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12Th IAEA Technical Meeting on Control, Data Acquisition and Remote Participation for Fusion Research WORKING MATERIAL ABSTRACTS AND MEETING MATERIAL 12th IAEA Technical Meeting on Control, Data Acquisition and Remote Participation for Fusion Research Daejeon, Republic of Korea, 13–17 May 2019 indico/event/180 DISCLAIMER This is not an official IAEA publication. The views expressed herein do not necessarily reflect thoseof the IAEA or its Member States. This document should not be quoted or cited as an official publication. The use of particular designations of countries or territories does not imply any judgement by the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries. The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA. 1 Preface Nuclear fusion is recognised as a long-term energy source. The International Atomic Energy Agency (IAEA) fosters the exchange of scientific and technical results in nuclear fusion research and devel- opment through its series of Technical Meetings and workshops. The 12th IAEA Technical Meeting on Control, Data Acquisition and Remote Participation for Fusion Research (CODAC 2019) aimed to provide a pre-eminent forum to discuss new developments and perspectives in the areas of control, data acquisition, data management and remote participation for nuclear fusion research around the world. The CODAC 2019 was organized by the IAEA, in cooperation with the Government of the Republic of Korea through the National Fusion Research Institute in Daejeon, Republic of Korea, 13–17 May 2019. Previous meetings in this series were held in Garching, Germany (1997), Lisbon, Portugal (1999), Padova, Italy (2001), San Diego, United States of America (2003), Budapest, Hungary (2005), Inuyama, Japan (2007), Aix-en-Provence, France (2009), San Francisco, United States of America (2011), Hefei, China (2013), Ahmedabad, India (2015) and Greifswald, Germany (2017). The main topics of the meeting were plasma control; machine control, monitoring, safety and remote manipulation; data acquisition and signal processing; database techniques for information storage and retrieval; advanced computing and massive data analysis; remote participation and virtual laboratory; and fast network technology and its application. This document has been assembled from the information submitted by the contributing authors via the IAEA-Indico conference management platform. Layout, editing, and typesetting was done by Pierre-Marie Brieda (France). The IAEA officer responsible for this document was M. Barbarino of the Division of Physical and Chemical Sciences. 2 International Programme Advisory Committee Mr Karl BEHLER (Chair) Germany Mr Axel WINTER (Co-chair) Germany Ms Sang-hee HAHN Republic of Korea Mr Adriano LUCHETTA Italy Mr Didier MAZON France Mr Hideya NAKANISHI Japan Ms Mikyung PARK ITER Organization Mr Wanderley PIRES DE SA Brazil Mr Harshad PUJARA India Ms Nathalie RAVENEL France Mr David SCHISSEL United States of America Mr Joshua STILLERMAN United States of America Mr John WATERHOUSE United Kingdom Mr Bingjia XIAO China Meeting Secretariat IAEA Scientific Secretary: IAEA Administration: Mr Matteo BARBARINO Ms Marion LINTER Division of Physical and Chemical Sciences Division of Physical and Chemical Sciences Department of Nuclear Sciences and Applications Department of Nuclear Sciences and Applications International Atomic Energy Agency International Atomic Energy Agency Vienna International Centre Vienna International Centre PO Box 100 PO Box 100 1400 VIENNA 1400 VIENNA AUSTRIA AUSTRIA Host Organization Contact Point: Mr Si-woo YOON National Fusion Research Institute 169-148 Gwahangno, Yuseong-gu DAEJEON REPUBLIC OF KOREA 34133 3 528 - Plenary Oral Machine Control, Monitoring, Safety and Remote Manipulation - 13 May 2019, 09:20 ITER Operation Application Systems for plant system integration and commissioning Mikyung Park ITER Organization ITER CODAC system from a software perspective is mainly composed of two software suites for the different purposes; firstly CODAC Core System (CCS) for plant system development and operation, and secondly CODAC Operation Application System (OP App) for orchestrating ITER operation and experiment executions. In aligned with the ITER project milestone, ITER CODAC team has lately more endeavored on the development of Operation Application System (OP App) and released a set of tools especially for plant system commissioning while covering functions of supervision & automation (SUP & AUTO), plant configuration (PSPS), real-time control framework (RTF) for PCS, data handling using Unified Data Access (UDA), remote participation (ORG & ODG), which were tested and evaluated at an operating tokamak, KSTAR following a whole sequence from pulse preparation to data service. This paper will describe the first delivery of ITER Operation Application System for plant system integration and commissioning and evaluation results as well as a future planning for plasma operation. Keywords: ITER, CODAC, Operation, Tokamak Page 4 488 - Plenary Oral Plasma Control - 13 May 2019, 09:40 EAST research activities on control and data toward CFETR Bingjia Xiao Institute of Plasma Physics, Chinese Academy of Sciences, China Chinese Fusion Experimental Tokamak Reactor (CFETR) started its engineering design since early 2018. A set of R&D aiming at establishing the technical basis for CFETR has also started recently. To meet CFETR design requirements, the domestic specific CFETR network and the design database has been established to facilitate the team data and design sharing and consistency. The document management system has been adapted from EAST which is originally from an open source sharing. For the plasma control, EAST is more and more focusing on the future CFETR needs. The fully separation of the vertical stability control with the shape, current and position control was demon- strated which is ITER and CFETR relevant. Multi-input and Multi-output control for the plasma shape and coil current was conducted, aiming at enhancing the control robustness. For the future CFETR and even DEMO scale reactor, traditional magnetics will inevitably meet the accuracy problem arising from neutron radiation and long-term drift. Optical shape reconstruction of the plasma shape will be one of solutions. A real-time data acquisition and reconstruction scheme has already primarily established and the optical setup has just initiated. To demonstrate the heat flux reduction to the divertor target which is one of the challenges for a fusion reactor, a set of control efforts have been conducted on EAST. The control of the flux expansion or an advanced plasma shape such as quasi-snowflake has shown a good heat flux reduction toward the divertor target.The radiation control on the SOL and divertor effectively reduced the total heat to the divertor target with the limited influence to the core plasma confinement. Moreover, plasma detachment control has been demonstrated by using the ion saturation current measured from Langmuir probe as the detachment indicator. For the plasma control system, a proposal has been given aiming at establishing a software base for the next generation PCS which meet the future CFETR requirements and catch up with information technology rapid growing. Page 5 443 - Plenary Oral Plasma Control - 13 May 2019, 10:00 Design and Development of a Cost Optimized Timing System for Steady state Superconducting Tokamak (SST-1) Jasraj Dhongde Institute for Plasma Research, India SST-1 timing system is a real time event based trigger generation and distribution system used for the synchronized operation of its various heterogeneous and distributed sub-systems during the plasma discharges. The VME based platform dependent old timing system is exhausted with spares inventory during long period of its existence and also had interface issues with the hardware advancement at subsystems end. The timing system physically consists of two types of modules i.e. central module and sub-system module. The timing and trigger distribution from central module to sub-systems are carried out by a star topology based optical fiber network. A platform independent, stand alone, 1U rack mountable timing system is designed, developed and tested based on Xilinx’s Artix-7 FPGAs for real time event (trigger) distribution amongst different sub-systems of SST-1. The new system design’s objectives being, to adopt same star topology as the old timing system, to support existing optical fiber network, to provide single interface to the heterogeneous sub systems and to have performance parameters, comparable to the old timing system with the minimal modifications on hardware as well as on software part at sub systems end. As stated earlier, in this new system, single central timing system module can support an interface of maximum of eight (8) subsystem modules in star configuration over optical fiber network. The central timing system module can generate pre-defined experiment event (trigger) sequence in real time with a resolution of 10µs and facilitates event logging at a resolution of 1µs. Each sub-system module can support eight (8) TTL inputs for asynchronous event generation and eight (8) TTL outputs for trigger pulse generation with a resolution of 1µs. Each experiment sequence on central timing module and trigger information on sub system timing modules are configured
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